Event Notification Report for September 23, 2019
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
09/22/2019 - 09/23/2019
Agreement State
Event Number: 54294
Rep Org: MARYLAND DEPT OF THE ENVIRONMENT
Licensee: GEO-TECHNOLOGY ASSOCIATES, INC
Region: 1
City: REISTERSTOWN State: MD
County:
License #: MD-25-038-01
Agreement: Y
Docket:
NRC Notified By: ALAN GOLDEY
HQ OPS Officer: OSSY FONT
Licensee: GEO-TECHNOLOGY ASSOCIATES, INC
Region: 1
City: REISTERSTOWN State: MD
County:
License #: MD-25-038-01
Agreement: Y
Docket:
NRC Notified By: ALAN GOLDEY
HQ OPS Officer: OSSY FONT
Notification Date: 09/25/2019
Notification Time: 16:09 [ET]
Event Date: 09/23/2019
Event Time: 15:20 [EDT]
Last Update Date: 11/17/2020
Notification Time: 16:09 [ET]
Event Date: 09/23/2019
Event Time: 15:20 [EDT]
Last Update Date: 11/17/2020
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
10 CFR Section:
Agreement State
Person (Organization):
CHRISTOPHER LALLY (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
CHRISTOPHER LALLY (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
EN Revision Imported Date: 11/18/2020
EN Revision Text: AGREEMENT STATE REPORT - LOST PORTABLE DENSITY GAUGE
The following was received from the Maryland Radiological Health Program via phone and email:
"On September 23, 2019 at 1520 EDT, the Maryland Department of the Environment Radiological Health Program (MDE/RHP) was contacted via telephone by the Assistant Radiation Safety Officer (ARSO) of Geo-Technology Associates, Inc. that a portable density gauge was missing. The gauge was identified as a CPN model MC-1DR, serial number MD50707960 with nominal activities of 10 mCi of Cs-137 and 50 mCi of Am-241:Be. The last leak test was performed on April 11, 2019.
"On September 23, 2019 at approximately 1300 EDT, the density gauge was placed in the bed of a pick-up truck by the gauge operator after making measurements starting earlier in the morning for a residential development project known as Fields at Worthington. The area is located near the intersection of Baublitz Road and Worthington Ridge Road, Reisterstown, MD. Work was suspended due to equipment failure on the job site not related to the density gauge. The gauge operator proceeded to drive back to the licensee's office. After driving approximately 1.5 miles from the jobsite, the gauge operator realized that the gauge was not placed in its transportation case and pulled over near Knox Avenue. The gauge was missing from the bed of the pick-up truck. The tailgate was in the down position. The gauge operator called the ARSO at approximately 1330 EDT to report the missing gauge.
"The ARSO and the construction site manager looked for the gauge in the surrounding neighborhood with no success. The event has been reported to Baltimore County Police. The Case Number is: 192661514.
"MDE/RHP will conduct a reactive investigation."
* * * UPDATE ON 11/17/20 AT 1538 EST FROM ATNATIWOS MESHESHA TO JEFFREY WHITED * * *
The following was received from the Maryland Radiological Health Program via email:
"On November 2, 2020 at 1040 EST the Maryland Department of the Environment, Radiological Health Program (MDE/RHP) was contacted via telephone by the Assistant Radiation Safety Officer (ARSO) of Geo-Technology Associates, Inc. that the portable density gauge that was missing on September 23, 2019, at the area located near the intersection of Baublitz Road and Worthington Ridge Road, Reisterstown, Maryland was found, dropped at the Baltimore County Waste Central Acceptance Facility (BCWCAF) located at Cockeysville, in Maryland (10275 Beaver Dam Road, Cockeysville, Maryland 21030). The gauge was identified as a CPN model MC-1DR, serial number MD50707960 with nominal activities of 10 mCi of Cs-137 and 50 mCi of Am-241/Be. The rod above the gauge scale was bent and damaged but the source shutter at bottom was found closed and a leak test performed on the same day, November 2, 2020, reported no leakage. The gauge was transferred to an authorized service provider for disposal on November 2, 2020."
Notified R1DO (Greives) and NMSS Event Notifications (email).
THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL
Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf
EN Revision Text: AGREEMENT STATE REPORT - LOST PORTABLE DENSITY GAUGE
The following was received from the Maryland Radiological Health Program via phone and email:
"On September 23, 2019 at 1520 EDT, the Maryland Department of the Environment Radiological Health Program (MDE/RHP) was contacted via telephone by the Assistant Radiation Safety Officer (ARSO) of Geo-Technology Associates, Inc. that a portable density gauge was missing. The gauge was identified as a CPN model MC-1DR, serial number MD50707960 with nominal activities of 10 mCi of Cs-137 and 50 mCi of Am-241:Be. The last leak test was performed on April 11, 2019.
"On September 23, 2019 at approximately 1300 EDT, the density gauge was placed in the bed of a pick-up truck by the gauge operator after making measurements starting earlier in the morning for a residential development project known as Fields at Worthington. The area is located near the intersection of Baublitz Road and Worthington Ridge Road, Reisterstown, MD. Work was suspended due to equipment failure on the job site not related to the density gauge. The gauge operator proceeded to drive back to the licensee's office. After driving approximately 1.5 miles from the jobsite, the gauge operator realized that the gauge was not placed in its transportation case and pulled over near Knox Avenue. The gauge was missing from the bed of the pick-up truck. The tailgate was in the down position. The gauge operator called the ARSO at approximately 1330 EDT to report the missing gauge.
"The ARSO and the construction site manager looked for the gauge in the surrounding neighborhood with no success. The event has been reported to Baltimore County Police. The Case Number is: 192661514.
"MDE/RHP will conduct a reactive investigation."
* * * UPDATE ON 11/17/20 AT 1538 EST FROM ATNATIWOS MESHESHA TO JEFFREY WHITED * * *
The following was received from the Maryland Radiological Health Program via email:
"On November 2, 2020 at 1040 EST the Maryland Department of the Environment, Radiological Health Program (MDE/RHP) was contacted via telephone by the Assistant Radiation Safety Officer (ARSO) of Geo-Technology Associates, Inc. that the portable density gauge that was missing on September 23, 2019, at the area located near the intersection of Baublitz Road and Worthington Ridge Road, Reisterstown, Maryland was found, dropped at the Baltimore County Waste Central Acceptance Facility (BCWCAF) located at Cockeysville, in Maryland (10275 Beaver Dam Road, Cockeysville, Maryland 21030). The gauge was identified as a CPN model MC-1DR, serial number MD50707960 with nominal activities of 10 mCi of Cs-137 and 50 mCi of Am-241/Be. The rod above the gauge scale was bent and damaged but the source shutter at bottom was found closed and a leak test performed on the same day, November 2, 2020, reported no leakage. The gauge was transferred to an authorized service provider for disposal on November 2, 2020."
Notified R1DO (Greives) and NMSS Event Notifications (email).
THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL
Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf
Power Reactor
Event Number: 54289
Facility: BRAIDWOOD
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: RICHARD ROWE
HQ OPS Officer: CATY NOLAN
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: RICHARD ROWE
HQ OPS Officer: CATY NOLAN
Notification Date: 09/23/2019
Notification Time: 14:15 [ET]
Event Date: 09/23/2019
Event Time: 11:06 [CDT]
Last Update Date: 09/23/2019
Notification Time: 14:15 [ET]
Event Date: 09/23/2019
Event Time: 11:06 [CDT]
Last Update Date: 09/23/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
ROBERT DALEY (R3DO)
ROBERT DALEY (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 100 | Power Operation | 0 | Hot Standby |
AUTOMATIC REACTOR TRIP DUE TO LOWERING STEAM GENERATOR LEVELS
"At 1106 CDT Braidwood Unit 1 experienced an automatic reactor trip due to lowering steam generator water levels following closure of the 1B steam generator feed water regulating valve.
"The cause of the 1B steam generator feedwater regulating valve failing closed is unknown at this time and is under investigation.
"Both trains of auxiliary feedwater started automatically following the reactor trip to maintain steam generator water levels.
"All systems responded as expected with the exception of intermediate range nuclear instrument N-36 which was identified as being undercompensated following the reactor trip. Both source range nuclear instruments were manually energized in accordance with station procedures. Steam generator power operated relief valves lifted momentarily and reseated as designed in response to the secondary transient due to the reactor trip. The main steam dump valves are in service to the main condenser to provide heat sink cooling. The plant is being maintained at normal operating pressure and temperature. AC power is being provided by offsite power with the diesel generators in stand by and all safety systems available. There is no impact to Unit 2.
"This report is being made per 10 CFR 50.72(b)(2)(iv)(B) for a RPS actuation, 4 hour notification, and per 10 CFR 50.72(b)(3)(iv)(A) for an automatic actuation of the auxiliary feedwater system, 8 hour notification.
"The NRC Resident Inspector has been informed."
"At 1106 CDT Braidwood Unit 1 experienced an automatic reactor trip due to lowering steam generator water levels following closure of the 1B steam generator feed water regulating valve.
"The cause of the 1B steam generator feedwater regulating valve failing closed is unknown at this time and is under investigation.
"Both trains of auxiliary feedwater started automatically following the reactor trip to maintain steam generator water levels.
"All systems responded as expected with the exception of intermediate range nuclear instrument N-36 which was identified as being undercompensated following the reactor trip. Both source range nuclear instruments were manually energized in accordance with station procedures. Steam generator power operated relief valves lifted momentarily and reseated as designed in response to the secondary transient due to the reactor trip. The main steam dump valves are in service to the main condenser to provide heat sink cooling. The plant is being maintained at normal operating pressure and temperature. AC power is being provided by offsite power with the diesel generators in stand by and all safety systems available. There is no impact to Unit 2.
"This report is being made per 10 CFR 50.72(b)(2)(iv)(B) for a RPS actuation, 4 hour notification, and per 10 CFR 50.72(b)(3)(iv)(A) for an automatic actuation of the auxiliary feedwater system, 8 hour notification.
"The NRC Resident Inspector has been informed."